JP2007132787A - Solidification processing method of radioactive waste - Google Patents

Abstract

<P>PROBLEM TO BE SOLVED: To provide a solidification processing method of radioactive wastes, capable of securing soundness of a disposal site over a long time, by controlling or preventing the generation of gas from a cement solidified matter due to radiolysis, while the cement solidified matter is buried underground and control or inhibit the increase in pressure, inside a containment vessel buried underground for disposal. <P>SOLUTION: The solidification processing method of radioactive waste comprising the steps of filling a containment vessel with a mixture containing a processing object matter containing radioactive wastes, a hydraulic inorganic solidifying material and water and solidifying the mixture to produce solidified matter comprises the solidification processing of filling the containment vessel with the mixture and solidifying the mixture to produce solidified matter, a drying process of heating and drying the solidified at a stage of uniaxial compression strength of not smaller than 1.5 MPa and not larger than 75% of a planned strength and the sealing process of putting a lid on the containment vessel and of sealing the vessel after the drying process. <P>COPYRIGHT: (C)2007,JPO&INPIT

Description

  The present invention relates to a method for solidifying radioactive waste, which is obtained by filling a container with a mixture containing a radioactive waste, a hydraulic inorganic solidifying material, and water and solidifying the mixture.

Radioactive waste generated from nuclear facilities, etc. is high-level radioactive waste with a high level of radioactivity discharged from spent fuel reprocessing, etc., 2000-200 mR / h (surface) as solid waste, liquid Wastes are classified into low-level radioactive wastes with a concentration of 10 ⁻³ to 10 ⁻⁶ μCi / ml and medium-level radioactive wastes with other intermediate levels. Depending on the radioactive level, treatments such as cement solidification, glass solidification, and melt solidification are performed. Among these, the cement solidification method is a method in which radioactive waste is filled in a drum can together with cement and water and solidified integrally, and is inexpensive and easy to process, so it is widely used for processing low-level radioactive waste. .

  In recent years, the possibility of cement solidification has also been studied for medium level radioactive waste, but if the radioactive level is high, there is a concern that hydrogen is generated from the cement solidified body and the pressure in the drum can be increased. In other words, moisture such as pore water and crystal water exists in the cement solidified body, but if the radionuclide concentration contained in the radioactive waste is relatively high, these waters are radiolyzed and hydrogen gas is generated. During long-term storage, it is assumed that the pressure inside the drum can be increased, affecting the soundness of the disposal site.

As a means for removing moisture in radioactive waste, a method of vacuum-drying the inside of a radioactive waste drum can containing radioactive waste has been proposed (for example, see Patent Document 1). However, this method merely dries the inside of a drum can in which radioactive waste such as metal waste is accommodated, and does not show the idea of drying the cement solidified body itself.
JP 2004-340814 A

  In the conventional solidification treatment method, when radioactive waste with a relatively high radionuclide concentration is solidified with a hydraulic inorganic solidification material such as cement, hydrogen gas is generated due to radiolysis of water, which may increase the pressure in the container. There is no established method for suppressing this gas generation.

  Therefore, the present invention suppresses or prevents the generation of gas from the solidified material due to radiolysis during the embedding of the solidified material obtained by solidifying the radioactive waste with the hydraulic inorganic solidifying material. It is an object of the present invention to provide a solidification method for radioactive waste that can suppress or prevent an increase in the pressure of the waste and ensure the soundness of the disposal site over a long period of time.

In order to achieve the above-mentioned object, the present invention is to solidify radioactive waste as a solidified material by filling a container containing a mixture containing a radioactive waste, a hydraulic inorganic solidifying material and water and solidifying the mixture. In the treatment method, a solidification step in which the admixture is filled in a container and solidified to form a solidified body, and the solidified body is dried by heating at a stage where the uniaxial compressive strength is 1.5 MPa or more and 75% or less of the planned strength. And a sealing step of sealing and sealing the storage container that has undergone the drying step.
Said drying is not restricted to the drying by heating, You may dry by pressure reduction and you may dry combining heating and pressure reduction.

  According to the present invention, during the embedding of a solidified material obtained by solidifying a radioactive waste with a hydraulic inorganic solidifying material, gas generation from the solidified material due to radiolysis is suppressed or prevented, and the inside of a storage container during a long-term embedding disposal Therefore, it is possible to provide a solidification method for radioactive waste that can prevent or prevent the increase in pressure and ensure the soundness of the disposal site over a long period of time.

  Hereinafter, embodiments of the present invention will be described in detail with reference to the drawings.

FIG. 1 is a flowchart showing a procedure of a radioactive waste solidification method according to an embodiment of the present invention. As shown in FIG. 1, a radioactive paste 1, a hydraulic inorganic solidified material 2, and water as necessary are mixed to produce a solidified paste (mixture) (S 1 a), and this solidified paste is stored. The container is stored (S1b).
It is also possible to mix in the storage container using an in-drum mixer or the like.

The radioactive waste 1 of the present invention is a medium level radioactive waste. In the present specification, the medium level radioactive waste is generated by radiolysis during long-term storage to generate hydrogen gas from the solidified body, and refers to a radioactive waste having a higher radioactive level than a so-called low level radioactive waste. The radioactive waste 1 may be in the form of a solid or liquid, and examples thereof include radioactive waste (so-called L1 waste) such as sodium sulfate waste liquid that is disposed at a marginal depth.
The hydraulic inorganic solidifying material 2 of the present invention solidifies the radioactive waste 1 and includes a cement-based solidifying material and the like. For example, various portland cements such as ordinary portland cement, early-strength portland cement, medium heat portland cement, low heat portland cement, various mixed cements such as blast furnace cement and fly ash cement, and various cements such as alumina cement can be used.

The hydraulic inorganic solidifying material 2 of the present invention can further contain an aggregate and / or a foaming agent as necessary.
As the aggregate, for example, sand, gravel, stone, alumina, silica fine powder, artificial lightweight aggregate, perlite, chamotte, iron powder, concrete waste, etc. can be used. By using the aggregate, it becomes easy to remove moisture from the formed solidified body by heating and / or decompression. Although the usage-amount of an aggregate is not specifically limited, 5-1500 weight part is preferable with respect to 100 weight part of hydraulic inorganic solidification materials (cement), and 100-1000 weight part is further more preferable. If the amount is less than 5 parts by weight, the effect of the aggregate that makes it easy to remove moisture from the formed solidified body by heating or the like is reduced, and if it exceeds 1500 parts by weight, strength development may be reduced.

  The foaming agent (foaming agent) is used for forming voids in the solidified body and obtaining cellular concrete (or mortar or cement paste). For example, amphoteric metals such as metallic aluminum powder, surfactants, Animal proteins, resin soaps, and the like can be used, and amphoteric metals such as metal aluminum powder and surfactants are preferred because they are effective when added in small amounts. By using a foaming agent (bubble agent), it becomes easy to remove moisture from the formed solidified body by heating and / or decompression.

  Amphoteric metals such as metallic aluminum powder utilize gas generated by chemical reaction. Although the usage-amount of aluminum powder is not specifically limited, 0.01-0.4 weight part is preferable with respect to 100 weight part of cement, and 0.05-0.3 weight part is further more preferable. When the amount is less than 0.01 part by weight, the foaming amount is small, and the effect of adding a foaming agent that it is easy to remove moisture from the formed solidified body by heating or the like becomes small. May become smaller.

Examples of the surfactant include an anionic surfactant, a cationic surfactant, an amphoteric surfactant, and a nonionic surfactant, which are excellent in foaming properties, stable in bubbles and large in fluidity. In terms, an anionic surfactant is preferred.
Examples of anionic surfactants include soaps such as sodium laurate and sodium stearate, sulfate esters such as sulfated oil and sulfated fatty acid esters, sulfonates such as alkylbenzene sulfonate and paraffin sulfonate, Examples include phosphate esters such as higher alcohol phosphates.
Although the usage-amount of an anionic surfactant is not specifically limited, 0.01-5 weight part is preferable with respect to 100 weight part of cement, and 0.1-1 weight part is further more preferable. When the amount is less than 0.01 part by weight, the foaming amount is small, and the effect of adding a foaming agent that the moisture is easily removed from the formed solidified body by heating or the like is small. There is a case.

In addition, various admixtures (materials) such as a fluidizing agent, a water reducing agent, an AE agent, and a high performance AE water reducing agent can be used as necessary.
The fluidizing agent is an additive added to improve the fluidity of the solidified paste, and examples thereof include inorganic fluidizing agents such as condensed sodium phosphate or a carbonate compound. These may be used alone or in combination of two or more. You may mix.
In addition, when the radioactive waste 1 is in a liquid state, it contains water, so there is a case where it is not necessary to add water separately. In the case where the radioactive waste 1 is in a liquid state, water may be added as necessary.

The solidified body formed in the storage container is cured (S2).
The curing period in the present invention is a period until the uniaxial compressive strength of the solidified body is 1.5 MPa or more and 75% or less of the planned strength, more preferably 1.5 MPa or more and 55% or less of the planned strength. It is a period until it becomes. In this specification, the planned strength refers to the uniaxial compressive strength of the solidified body having a curing period (material age) of 28 days. In the present specification, the uniaxial compressive strength is measured according to JIS A1108: a test method for compressive strength of concrete.
By setting the curing period to a period in which the uniaxial compressive strength of the solidified body is 1.5 MPa or more and 75% or less of the planned strength, it is easy to remove moisture from the formed solidified body by heating and / or decompression. become.

  If the uniaxial compressive strength of the solidified body is less than 1.5 MPa, the water is removed from the solidified body by heating or the like before the hydraulic inorganic solidified material 2 is sufficiently hydrated with water. Becomes insufficient, and the strength development is reduced. When the uniaxial compressive strength of the solidified body exceeds 75% of the planned strength, the effect of easily removing moisture from the formed solidified body by heating or the like becomes small.

  The relationship between curing days and uniaxial compressive strength varies depending on the cement type and temperature. When the curing temperature is 15 to 20 ° C. using early-strength Portland cement, the curing days for which the uniaxial compressive strength is 75% of the planned strength correspond to 7 days. In addition, under the same conditions, the number of days of curing at which the uniaxial compressive strength becomes 55% of the planned strength corresponds to 3 days.

The curing method is not particularly limited, and for example, any method such as air drying curing, wet air curing, heating accelerated curing (steam curing, etc.) may be adopted, but the storage container is covered. It is preferable to perform static curing.

  Water is removed (dried) from the solidified body by heating and / or decompressing (S3). The off-gas 3 generated at this time is introduced into the off-gas treatment means to be described later when the water vapor in the off-gas 3 is removed by adsorption, condensation, etc. by the water separation means to be described later (S4). The radionuclide is removed by adsorption, combustion, etc. (S5).

The heat treatment temperature is preferably 50 ° C. or higher and lower than 500 ° C. If it is less than 50 ° C., the removal of moisture from the solidified body is insufficient, and if it is 500 ° C. or higher, calcium hydroxide in the solidified body is decomposed and the internal structure of the solidified body may be damaged. However, since alumina cement is mainly composed of calcium aluminate and has heat resistance, it is preferably 100 ° C. or higher and 1600 ° C. or lower.
The heat treatment time is preferably 8 hours or more and 20 hours or less. If the heat treatment time is less than 8 hours, the removal of moisture from the solidified body may be insufficient. In addition, since the amount of water removed is almost saturated when the heat treatment time is about 20 hours, the effect of removing water by heating is reduced when it exceeds 20 hours.

  The reduced pressure is preferably a treatment pressure of 0 kPa to 1 kPa. When it exceeds 1 kPa, the removal of moisture from the solidified body may be insufficient.

After the above-mentioned solidified body is sufficiently heated and / or decompressed to remove moisture (S3), the storage container is covered and sealed (S6). The storage container is sealed by welding the outer periphery of the cover or by interposing a sealing material between the cover and the storage container. As a result, it is possible to prevent water from entering the storage container for a long time even after disposal.
The storage container storing the solidified body is covered and sealed, and then buried in the buried disposal facility (S7).

In this embodiment configured as described above, a solidified body obtained by solidifying the radioactive waste 1 with the hydraulic inorganic solidified material 2 is formed, and the solidified body is embedded by removing moisture by sufficiently heating or the like. It is possible to suppress or prevent gas generation from the solidified body due to radiolysis.
At that time, by setting the curing period to a period in which the uniaxial compressive strength of the solidified body is 1.5 MPa or more and 75% or less of the planned strength, moisture is removed from the formed solidified body by heating and / or decompression. It becomes easy. Further, it is formed by forming a solidified body using an aggregate and / or a foaming agent, and setting the uniaxial compressive strength of the solidified body from 1.5 MPa or more to 75% or less of the planned strength. It becomes easier to remove moisture from the solidified body by heating and / or decompression.

  According to the present embodiment, since the gas generation from the solidified body can be suppressed or prevented by radiolysis during the embedding of the solidified body, even if the radioactive waste has a relatively high radionuclide concentration, The increase in pressure in the storage container during the disposal of the container can be suppressed or prevented, and the soundness of the disposal site can be ensured over a long period of time.

Next, a radioactive waste solidification processing apparatus according to an embodiment of the present invention will be described.
FIG. 2 is a diagram showing a configuration of a radioactive waste solidification processing apparatus according to an embodiment of the present invention. The radioactive waste solidification treatment device 10 includes a mixer 11, a storage container 12, a transfer device 13, a moisture removal device 14, a moisture separation means 15, an off-gas treatment means 16, and a sealing means (not shown). It is configured.

The mixer 11 mixes the solidified paste containing the radioactive waste 1 and the hydraulic inorganic solidified material 2 and functions as a mixing means. The mixer 11 is not specifically limited, For example, various mixers, such as an omni mixer, a bread-type mixer, a biaxial kneader mixer, can be used.
The storage container 12 stores the solidified paste (mixture) mixed by the mixer 11 and is, for example, a drum can. For example, carbon steel, stainless steel, zirconium, titanium, copper, or the like can be used as a constituent material of the storage container 12. When the inside of the storage container 12 is vacuum-dried, it is preferable to use a pressure resistant container.
In addition, you may mix in the storage container 12 using an in drum mixer.

  The transfer device 13 transfers the storage container 12 storing the solidified paste (mixture) or the solidified material to the moisture removing device 14, and is, for example, a belt conveyor. It can also be transferred by a forklift or the like.

The moisture removing device 14 accommodates the storage container 12 in which the solidified paste is stored, and after curing, removes the moisture of the solidified body in the storage container 12 by heating and / or depressurization. / Or provided with vacuum evacuation means.
A heating furnace is not specifically limited, For example, various heating furnaces, such as a resistance heating furnace and an induction heating furnace, can be used.
The vacuum exhaust means is not particularly limited, and for example, various vacuum pumps can be used.

  The water removal by the reduced pressure can be performed by the following method. In the first method, the storage container 12 is covered with a dedicated lid for vacuum drying, and the inside of the storage container 12 is vacuum-dried by a vacuum exhaust means. In the second method, the inside of the storage container 12 is vacuum-dried by vacuum evacuation means using a dedicated lid for vacuum drying, and the inside of the moisture removing device 14 is also vacuum-dried by vacuum evacuation means. In the third method, the container 12 is not covered and the inside of the moisture removing device 14 is vacuum-dried by a vacuum exhaust means.

  The water separation means 15 is a device that removes water vapor by adsorption or condensation from the off-gas 3 generated when water is removed from the solidified body by heating and / or reduced pressure. For example, a cooling tower, a desiccant, etc. I have.

The cooling tower is a device that cools the water vapor in the off-gas 3 and recovers the water by making it liquid or solid. The desiccant is a chemical used to remove moisture in the offgas 3, and examples thereof include molecular sieves and concentrated sulfuric acid. The moisture separation means 15 can prevent a decrease in function due to dew condensation of the off-gas treatment means 16 and can remove moisture containing tritium existing as H ₂ O (that is, T ₂ O or HTO).

  The off-gas treatment means 16 is a device that removes radionuclides present in the off-gas 3 by adsorption, combustion, or the like. The off-gas may contain hydrogen, carbon dioxide, volatile organic carbon compounds, chlorine and iodine radionuclides (tritium, C-14, Cl-36, I-129).

  Tritium contained in the hydrogen is removed by the off-gas treatment means 16 equipped with an oxidation catalyst that converts hydrogen into water. The oxidation catalyst for converting hydrogen into water is a catalyst comprising one or more kinds of metals such as Pt, Pd, Ru, Rh, Ir, Os, Ag, Au, Re, Cu, Ni, Co, and Zn. Hydrogen gas is reacted with oxygen under a heating condition using a catalyst such as Pt, and the produced water is recovered.

  C-14 contained in the volatile organic carbon compound is removed by the off-gas treatment means 16 equipped with a device for oxidizing the organic carbon compound gas. An apparatus for oxidizing an organic carbon compound gas is, for example, an oxidation catalyst comprising any one or more kinds of metals such as Pt, Pd, Ru, Rh, Ir, Os, Ag, Au, Re, Cu, Ni, Co, and Zn. The organic carbon compound gas is heated and oxidized to generate carbon dioxide. The carbon dioxide thus produced is recovered as carbonate ions by a scrubber using an alkaline solution together with carbon dioxide generated from the solidified product.

  Cl-36 and I-129 contained in a halogen gas such as chlorine and iodine are adsorbed and removed by the off-gas treatment means 16 equipped with activated carbon.

  The sealing means (not shown) seals the storage container 12 with a lid.

  The solidified paste containing the radioactive waste 1 and the hydraulic inorganic solidified material 2 is mixed by the mixer 11 (S1a), and this solidified paste (mixture) is stored in the storage container 12 (S1b). The storage container 12 in which (mixture) is stored is transferred into the moisture removing device 14 by the transfer device 13 and is cured for a necessary period (S2) to form a solidified body. Water is removed (dried) from the solidified body in the storage container 12 by heating and / or decompressing (S3). The offgas 3 generated from the solidified body by this heating and / or decompression is removed of water vapor by the water separation means 15 (S4), and then the radionuclide in the offgas 3 is removed by the offgas processing means 16 (S5). The storage container 12 filled with the solidified body from which moisture has been removed by the moisture removing device 14 is covered with a sealing means. The storage container 12 is sealed by welding the outer periphery of the cover or by interposing a sealing material between the cover and the storage container 12 (S6). The sealed storage container 12 is buried in a buried disposal facility (S7).

  EXAMPLES Next, although an Example demonstrates this invention, this invention is not limited to these Examples.

Example 1
Alumina cement (made by TOSHIBA CERAMIC CO., LTD.) 650 parts by weight and 350 parts by weight of tap water are mixed with a mixer, and the solidified paste (admixture) is separated into a mold having a height of 10 cm and a diameter of 5 cm. After curing, a solidified body having a uniaxial compressive strength of 9.6 MPa (75% of the planned strength of 12.8 MPa) was obtained. The obtained solidified body was heated at 120 ° C. to remove moisture.

(Example 2)
100 parts by weight of alumina cement (manufactured by Toshiba Ceramics Co., Ltd.), 100 parts by weight of silica fine powder (manufactured by Toshiba Ceramics Co., Ltd.), 100 parts by weight of alumina fine powder (manufactured by Toshiba Ceramics Co., Ltd.), 700 parts by weight of Chamotte (manufactured by Toshiba Ceramics Co., Ltd.) Then, 250 parts by weight of 0.1% condensed sodium phosphate aqueous solution was mixed, and the solidified paste (mixture) was separated into a mold having a height of 10 cm and a diameter of 5 cm, and allowed to stand for 24 hours, uniaxial compressive strength Of 1.0 MPa (50% of the planned strength of 2.0 MPa) was obtained. The obtained solidified body was heated at 120 ° C. to remove moisture.

(Comparative Example 1)
Moisture was removed from the solidified body in the same manner as in Example 1 except that the film was allowed to stand for 30 days and the uniaxial compressive strength at that time was 12.8 MPa.

(Comparative Example 2)
Moisture was removed from the solidified body in the same manner as in Example 2 except that the film was allowed to stand for 30 days and the uniaxial compressive strength at that time was 2.7 MPa.

  Table 1 shows the raw material composition table of each example and comparative example.

  The result is shown in FIG. FIG. 3 is a graph showing a change with time of the remaining water amount / initial added water amount (%) when the solidified bodies of Examples 1 and 2 and Comparative Examples 1 and 2 were heated at 120 ° C. to remove moisture.

Example 1 and Comparative Example 1, and Example 2 and Comparative Example 2 having the same composition are compared. It was recognized that the solidified bodies having a curing time of 24 hours (Examples 1 and 2) had a higher moisture removal rate than the solidified bodies having a curing period of 30 days (Comparative Examples 1 and 2). That is, the solidified body (Examples 1 and 2) having a uniaxial compressive strength at the end of curing of 1.5 MPa or more and 75% or less of the planned strength has a uniaxial compressive strength at the end of curing of 1.5 MPa or more and a planned strength of 75 Compared with solidified bodies (Comparative Examples 1 and 2) not in the range of not more than%, the moisture removal rate was high, and moisture removal by heating was easy.
In addition, the solidified body containing aggregate (Example 2, Comparative Example 2) has a higher water removal rate than the solidified body containing no aggregate (Example 1 and Comparative Example 1), and easily contains moisture. It was found that can be removed.
The solidified body (Example 2) having a curing time of 24 hours, that is, a uniaxial compressive strength at the end of the curing of 1.5 MPa or more to 75% or less of the planned strength and containing aggregate has a moisture removal rate. It was the highest and water removal by heating was the easiest.
(Uniaxial compressive strength test)
The uniaxial compressive strength of the solidified body after the heat treatment at 120 ° C. in Example 1 was 21.4 MPa. A solidified body having a curing time of 24 hours (a solidified body having a uniaxial compressive strength of 1.5 MPa or more at the end of curing and 75% or less of the planned strength) is 1.5 MPa, which is an evaluation reference value even if the curing time is short. It was confirmed that

It is a flowchart which shows the procedure of the solidification processing method of the radioactive waste which concerns on one Embodiment of this invention. It is a figure which shows the structure of the solidification processing apparatus of the radioactive waste which concerns on one Embodiment of this invention. It is a figure which shows a time-dependent change of the amount of residual water / initial addition water amount (%) when the solidified body of each Example and each comparative example is heated at 120 degreeC.

Explanation of symbols

DESCRIPTION OF SYMBOLS 1 ... Radioactive waste, 2 ... Hydraulic inorganic solidification material, 3 ... Off gas, 10 ... Solidification processing apparatus of radioactive waste, 11 ... Mixer, 12 ... Storage container, 13 ... Transfer apparatus, 14 ... Moisture removal apparatus, 15 ... Moisture separation means, 16 ... off-gas treatment means.

Claims (10)

In the solidification method of radioactive waste to be solidified by filling a container with a mixture containing a radioactive waste to be treated, a hydraulic inorganic solidifying material and water and solidifying the mixture,
A solidification step of filling the admixture into a container and solidifying it into a solidified body; and
A drying step of drying the solidified body by heating at a stage where the uniaxial compressive strength is 1.5 MPa or more and 75% or less of the planned strength;
A sealing step of sealing and sealing the storage container that has undergone the drying step;
A solidification method for radioactive waste, comprising: In the solidification method of radioactive waste to be solidified by filling a container with a mixture containing a radioactive waste to be treated, a hydraulic inorganic solidifying material and water and solidifying the mixture,
A solidification step of filling the admixture into a container and solidifying it into a solidified body; and
A drying step of drying the solidified body under reduced pressure at a stage where the uniaxial compressive strength is 1.5 MPa or more and 75% or less of the planned strength;
A sealing step of sealing and sealing the storage container that has undergone the drying step;
A solidification method for radioactive waste, comprising: In the solidification method of radioactive waste to be solidified by filling a container with a mixture containing a radioactive waste to be treated, a hydraulic inorganic solidifying material and water and solidifying the mixture,
A solidification step of filling the admixture into a container and solidifying it into a solidified body; and
A drying step of drying the solidified body by heating under reduced pressure at a stage where the uniaxial compressive strength is 1.5 MPa or more and 75% or less of the planned strength;
A sealing step of sealing and sealing the storage container that has undergone the drying step;
A solidification method for radioactive waste, comprising:   The method for solidifying radioactive waste according to claim 1 or 3, wherein the drying by heating is performed at a temperature of 50 ° C or more for 8 hours or more.   The method for solidifying radioactive waste according to claim 2 or 3, wherein the drying by the reduced pressure is performed under a reduced pressure of 1 kPa or less.   The method for solidifying radioactive waste according to claim 1, wherein the hydraulic inorganic solidified material includes aggregate.   The method for solidifying radioactive waste according to claim 1, wherein the hydraulic inorganic solidifying material contains a foaming agent.   The method for solidifying radioactive waste according to any one of claims 1 to 7, wherein the object to be treated, the hydraulic inorganic solidifying material, and water are mixed in the storage container.   The method for solidifying radioactive waste according to claim 1, wherein the lid is liquid-tightly fixed to the storage container by welding or a sealing material.   The solidified treatment of radioactive waste according to any one of claims 1 to 9, wherein water vapor generated in the drying step is guided to a treatment device by an air flow and separated from the air flow by adsorption or condensation. Method.

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